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Proceedings Papers

Research on Improving the Science Popularization System of Nuclear-Related Projects in China

Zhenhua Zhang, Li Zhu
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90546
https://doi.org/10.1115/ICONE29-90546
View Paper titled, Research on Improving the Science Popularization System of Nuclear-Related Projects in China
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Topics: Accidents, Chain, China, Climate, Coal power, Education, Engineering disciplines, Engineering teachers, Governments, Nuclear industry
Proceedings Papers

A Finnish District Heating Reactor: Background and General Overview

Jaakko Leppänen, Seppo Hillberg, Ville Hovi, Rebekka Komu, Joona Kurki, Unna Lauranto, Ahti Oinonen, Jussi Peltonen, Antti Rintala, Ville Tulkki, Riku Tuominen, Ville Valtavirta
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64346
https://doi.org/10.1115/ICONE28-64346
View Paper titled, A Finnish District Heating Reactor: Background and General Overview
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Topics: Central heating, Design, Coal, Governments, Heat, Boilers, Carbon, Climate, Containment, Energy generation
Proceedings Papers

Impact of Climate Change on EDF’s Nuclear Facilities: Climate Watch Approach

L. Guinard, S. Parey, H. Cordier, L. Grammosenis
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A021, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16186
https://doi.org/10.1115/ICONE2020-16186
View Paper titled, Impact of Climate Change on EDF’s Nuclear Facilities: Climate Watch Approach
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Topics: Climate, Climate change, Hazards, Nuclear power stations, Safety
Proceedings Papers

Case Study Analyses of Flaw Growth and Tolerance of Stainless Steel Canisters in Marine Environment

Chang Heui-Yung
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A094, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67301
https://doi.org/10.1115/ICONE25-67301
View Paper titled, Case Study Analyses of Flaw Growth and Tolerance of Stainless Steel Canisters in Marine Environment
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Topics: Stainless steel, Storage, Temperature, Climate, Cracking (Materials), Fracture (Process), Nuclear fuels, Nuclear power stations, Shells, Spent fuel storage
Proceedings Papers

Reliability of PCCS in AP1000 Based on Accident Development

Yu Yu, Shengfei Wang, Fenglei Niu
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A007, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60155
https://doi.org/10.1115/ICONE24-60155
View Paper titled, Reliability of PCCS in AP1000 Based on Accident Development
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Topics: Accidents, Reliability, Containment, Heat, Pressure, Failure, Nuclear power stations, Steam, System failures, Temperature
Proceedings Papers

Benchmark Accelerated Aging of Harvested Hypalon/EPR and CSPE/XLPE Power and I&C Cable in Nuclear Power Plants

Robert C. Duckworth, Emily Frame, Leonard S. Fifield, Samuel W. Glass, III
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T01A007, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60311
https://doi.org/10.1115/ICONE24-60311
View Paper titled, Benchmark Accelerated Aging of Harvested Hypalon/EPR and CSPE/XLPE Power and I&C Cable in Nuclear Power Plants
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Topics: Cables, Nuclear power stations, Insulation, Light water reactors, Mechanical properties, Radiation (Physics), Temperature, Amperes, Climate, Ethylene-propylene rubber
Proceedings Papers

Feasibility of Enhanced Estimation of PWR Primary Parameters: Twin Experiments for Assessing Data Assimilation Benefits (0D-Model With a Monte-Carlo Approach on Pseudo-Real Data)

Thibaud Mercier, Jean-Melaine Favennec, Alexandre Girard
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T01A002, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30118
https://doi.org/10.1115/ICONE22-30118
View Paper titled, Feasibility of Enhanced Estimation of PWR Primary Parameters: Twin Experiments for Assessing Data Assimilation Benefits (0D-Model With a Monte-Carlo Approach on Pseudo-Real Data)
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Topics: Pressurized water reactors, Climate, Nuclear reactor coolants, Flow (Dynamics), Meteorology, Safety, Temperature distribution, Uncertainty
Proceedings Papers

The Use of Risk-Informed Inspection Approaches of Ukraine

Bogdan Hryshchenko, Mykhailo Polianskyi, Anatoliy Nosovskyy, Oleksandr Sevbo
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A032, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16242
https://doi.org/10.1115/ICONE21-16242
View Paper titled, The Use of Risk-Informed Inspection Approaches of Ukraine
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Topics: Risk-based inspection, Inspection, Risk, Safety, Nuclear power stations, Design, Accidents, Climate, Damage, Failure
Proceedings Papers

CANDU Position and Prospect in Chinese Nuclear Fuel Cycle

Zhenhua Zhang, Mingjun Chen, Peide Zhou, Qing Li, Zhiliang Meng, Guowei Zhang
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A046, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16727
https://doi.org/10.1115/ICONE21-16727
View Paper titled, CANDU Position and Prospect in Chinese Nuclear Fuel Cycle
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Topics: Nuclear fuel cycle, Nuclear power, Uranium, Certainty, China, Climate, Recycling, Sustainable development, Thermal reactors
Proceedings Papers

Self-Propelling Cooling Systems: Back-Fitting Passive Cooling Functions to Existing Nuclear Power Plants

Dominik von Lavante, Dietmar Kuhn, Ernst von Lavante
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 663-672, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54382
https://doi.org/10.1115/ICONE20-POWER2012-54382
View Paper titled, Self-Propelling Cooling Systems: Back-Fitting Passive Cooling Functions to Existing Nuclear Power Plants
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Topics: Cooling, Cooling systems, Fittings, Nuclear power stations, Temperature, Heat, Spent nuclear fuels, Pipes, Electricity (Physics), Emergencies
Proceedings Papers

Feedwater Heater Study for an Extended Power Uprate at a Nuclear Power Station

Eric Svensson, Aravind Krishnamoorthy, Michael Catapano, Michael Coakley, Dan Thomas
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 197-202, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54953
https://doi.org/10.1115/ICONE20-POWER2012-54953
View Paper titled, Feedwater Heater Study for an Extended Power Uprate at a Nuclear Power Station
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Topics: Feedwater, Nuclear power stations, Power uprate, Climate, Computational methods, Cycles, Design, Engineering standards, Failure, Heat
Proceedings Papers

Output-Feedback Load-Following Control of Nuclear Reactors Based on a Dissipative High Gain Filter

Zhe Dong, Xiaojin Huang, Liangju Zhang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 619-626, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29056
https://doi.org/10.1115/ICONE18-29056
View Paper titled, Output-Feedback Load-Following Control of Nuclear Reactors Based on a Dissipative High Gain Filter
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Topics: Feedback, Filters, Nuclear reactors, Stress, Control equipment, State feedback, Climate, Combustion, Computer simulation, Computer technology
Proceedings Papers

A Computer Program Predicting Steady-State Performance of a Nuclear Research Reactor’s Cooling System

Kamel Sidi Ali
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 1-6, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22009
https://doi.org/10.1115/ICONE10-22009
View Paper titled, A Computer Program Predicting Steady-State Performance of a Nuclear Research Reactor’s Cooling System
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Topics: Computer software, Cooling systems, Cooling towers, Nuclear research, Simulation, Steady state, Nuclear reactors, Climate, Cooling, Heat
Proceedings Papers

Statistical Assessment of Operating Experiences of Power Reactors in France, Japan, and the United States

Hitoshi Sakamoto
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 663-671, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49173
https://doi.org/10.1115/ICONE12-49173
View Paper titled, Statistical Assessment of Operating Experiences of Power Reactors in France, Japan, and the United States
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Topics: Climate, Nuclear power, Probabilistic safety assessment, Regression analysis
Proceedings Papers

Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Direct Coupling Between Probabilistic and Finite-Element Codes to Model Sensitivity to Key Thermo-Hydraulic Variability

Etienne de Rocquigny, Yoan Chevalier, Silvia Turato, Eric Meister
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 305-312, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49301
https://doi.org/10.1115/ICONE12-49301
View Paper titled, Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Direct Coupling Between Probabilistic and Finite-Element Codes to Model Sensitivity to Key Thermo-Hydraulic Variability
Open the PDF for Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Direct Coupling Between Probabilistic and Finite-Element Codes to Model Sensitivity to Key Thermo-Hydraulic Variability in another window
Topics: Failure, Finite element analysis, Reactor vessels, Safety, Vessels, Thermomechanics, Probability, Temperature, Transients (Dynamics), Accidents